25 results on '"Hanson, Bruce C."'
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2. The effect of size and shape of annular centrifugal contactors upon hydrodynamics and mass transfer using HNO3-TBP/OK
3. Accumulation of Particles in an Annular Centrifugal Contactor Cascade and the Effect upon the Extraction of Nitric Acid
4. A self-optimised approach to synthesising DEHiBA for advanced nuclear reprocessing, exploiting the power of machine-learning
5. Aqueous hydroxylation mediated synthesis of crystalline calcium uranate particles
6. Effect of Scale-Up on Residence Time and Uranium Extraction on Annular Centrifugal Contactors (ACCs)
7. Mathematical modelling of the pre-oxidation of a uranium carbide fuel pellet
8. Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects
9. Synthesis of Calcium Monouranate Particles via an Aqueous Route
10. CFD Analysis of Liquid-Liquid Extraction Pulsed Sieve-Plate Extraction Columns
11. Prediction of Horizontal Gas–Liquid Segregated Flow Regimes with an All Flow Regime Multifluid Model
12. Process intensification of element extraction using centrifugal contactors in the nuclear fuel cycle
13. The development of centrifugal contactors: Next generation solvent extraction equipment for advanced reprocessing of nuclear fuels.
14. Optimisation of the Hydrophilic Conditioning of Amidoximated Polymers and Evaluation of their Uranium Adsorption Capability.
15. End point determination for spent nuclear fuel drying operations
16. A benchtop comparison of drying methods relevant to failed spent nuclear fuel
17. Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects.
18. Vacuum drying of advanced gas reactor fuel
19. ChemInform Abstract: Aqueous Hydroxylation Mediated Synthesis of Crystalline Calcium Uranate Particles.
20. A two-dimensional, finite-difference model of the oxidation of a uranium carbide fuel pellet
21. A Two-Dimensional, Finite-Difference Model of the Oxidation of a Uranium Carbide Fuel Pellet.
22. Editorial
23. Computational engineering for nuclear solvent extraction equipment
24. Transitioning of spent advanced gas reactor fuel from wet to dry storage
25. Syntheses of ternary oxyhydrates and oxides in the calcium-uranium system : stoichiometric influences on their structural affinity, precipitation mechanisms, and solid-state transformations
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